Fabrication Technology for MOX Fuel Containing AmO2 by an In-cell Remote Process

YOSHIMOCHI, Hiroshi; NEMOTO, Masanao; MONDO, Kenji; Koyama, Shin-ichi; Namekawa, T.

doi:10.3327/jnst.41.850

Cited by 26 publications

(23 citation statements)

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“…Research and development of Am-containing MOX (Am-MOX), (U,Pu,Am)O 2-x , which is a representative LDF, was started in the early 1990s in a laboratory of Japan Atomic Energy Agency Yoshimochi et al [7]. As almost nothing was known about the effects of Am addition on various characteristics of the standard MOX, we had to grope for the best solution by ourselves.…”

Section: Fabrication Technology With Remote Operationmentioning

confidence: 99%

“…Since characteristics of Am-MOX fabrication were not known at the beginning, fundamental fabrication tests were carried out Yoshimochi et al [7]. The fabrication procedure was based on the traditional powder metallurgy that is adopted for the standard MOX, as the procedure is relatively simple and compatible with the remote operation.…”

Section: Fabrication Technology With Remote Operationmentioning

confidence: 99%

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Innovative oxide fuels doped with minor actinides for use in fast reactors

Osaka¹,

Miwa²,

Tanaka³

et al. 2007

WIT Transactions on Ecology and the Environment, Vol 105

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Research and development of innovative oxide fuels doped with minor actinides for use in fast reactors are underway. Management of minor actinides in a fast reactor fuel cycle is a key technology for successful realization of a sustainable energy supply with a low impact on the environment. Americium-doped oxide fuels are focused on as representative of minor actinides-containing fuel. Two types of fuels were designed and fabrication tests were carried out. Fundamental properties were also investigated. Results can effectively be reflected to establishment of the fast reactor cycle with minor actinides.

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Section: Fabrication Technology With Remote Operationmentioning

confidence: 99%

Section: Fabrication Technology With Remote Operationmentioning

confidence: 99%

Innovative oxide fuels doped with minor actinides for use in fast reactors

Osaka¹,

Miwa²,

Tanaka³

et al. 2007

WIT Transactions on Ecology and the Environment, Vol 105

View full text Add to dashboard Cite

show abstract

“…Renard (1995a) suggested that the limitations in recycle were not in fuel fabrication since hot cells could provide adequate personnel protection, but in the core physics-neutronics issues of placing the actinide blended fuel in the reactor. Yoshimochi (2004) described fabrication of a MOX fuel with 3% americium oxide included. For that work they concluded that they required hot cell operation because handling the gamma-emitting americium in a glovebox was difficult.…”

Section: Radiolysis Of Solutionsmentioning

confidence: 99%

Summary of Off-Normal Events in US Fuel Cycle Facilities for AFCI Applications

Cadwallader¹,

Piet²,

Sheetz³

et al. 2005

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This report is a collection and review of system operation and failure experiences for facilities comprising the fission reactor fuel cycle, with the exception of reactor operations. This report includes mines, mills, conversion plants, enrichment plants, fuel fabrication plants, transportation of fuel materials between these centers, and waste storage facilities. Some of the facilities discussed are no longer operating; others continue to produce fuel for the commercial fission power plant industry. Some of the facilities discussed have been part of the military's nuclear effort; these are included when the processes used are similar to those used for commercial nuclear power. When reading compilations of incidents and accidents, after repeated entries it is natural to form an opinion that there exists nothing but accidents. For this reason, production or throughput values are described when available. These adverse operating experiences are compiled to support the design and decisions needed for the Advanced Fuel Cycle Initiative (AFCI). The AFCI is to weigh options for a new fission reactor fuel cycle that is efficient, safe, and productive for US energy security. iv v SUMMARYThis report is a collection of historical data on the US fission fuel cycle facilities, focusing on the incidents and off-normal events that have occurred. These data are useful input to the Advanced Fuel Cycle Initiative (AFCI), which is to weigh options for a new fission reactor fuel cycle that is efficient, safe, and productive for US energy security. Only published reports and papers have been researched; no classified or sensitive data were used during this report preparation.The intent of this report is to provide a summary of accidents and events that have occurred in the nuclear fuel cycle for use as operating experience feedback to the design of future fuel cycle facilities that support the commercial nuclear power industry. The nuclear fuel cycle is a mixture of industrial processes. Initially, solution mining that produces the uranium feedstock is an industrial process similar to well drilling in the petroleum industry and it has similar hazards of drilling and pumping fluid. Purifying the uranium solution by solvent extraction is a chemical treatment process similar to different types of ore purification performed in other industries and has the hazards inherent with chemical process plants.Uranium enrichment is performed chemically and mechanically, which in principle is similar to the activities and hazards of the chemical process, petroleum, and other industries. During the enrichment step, nuclear criticality safety concerns begin to arise, which is a complication not found in other industries. Fuel pellet and fuel element fabrication is similar to many manufacturing processes that produce large numbers of high precision parts. Fuel fabrication assembly lines, like those in many industries, are partly automated and partly operated by workers. Uranium fuel has very low radioactivity, so the handling concerns dwell ...

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“…[1][2][3] Post-irradiation examinations have been started to evaluate the irradiation behaviour. 4) The ''SUPERFACT'' 5) experiment was promoted as a typical program to evaluate incineration and transmutation of neptunium (Np) and Am in MOX fuels irradiated in the French fast reactor Phenix.…”

Section: Introductionmentioning

confidence: 99%

Chemical Analysis of Americium Samples Irradiated under Fast Neutron Spectra

Koyama

Mitsugasira

2008

Journal of Nuclear Science and Technology

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In order to evaluate the transmutation behavior of americium under fast neutron spectra, two irradiated 241 Am samples (No. 69, No. 70) were analyzed by radiochemical methods. About 100 mg of 241 Am (Am oxide, 99.9%) samples encapsulated in a small vanadium capsule were irradiated in the experimental fast reactor JOYO for 275 effective full power day (EFPD) by the fast neutron flux of 1:08 Â 10 15 (No. 69, in the reflector region) and 3:25 Â 10 15 (No. 70, at the center core) nÁcm À2 s À1 (E ! 0:1 MeV). After dissolution of these samples, americium, curium, and plutonium were chemically separated and the isotopic composition was determined by alpha and gamma-ray spectrometries and mass spectroscopy.

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Fabrication Technology for MOX Fuel Containing AmO2 by an In-cell Remote Process

Cited by 26 publications

References 1 publication

Innovative oxide fuels doped with minor actinides for use in fast reactors

Innovative oxide fuels doped with minor actinides for use in fast reactors

Summary of Off-Normal Events in US Fuel Cycle Facilities for AFCI Applications

Chemical Analysis of Americium Samples Irradiated under Fast Neutron Spectra

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